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Publication

Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization

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Publication Type
Journal
Journal Name
Nuclear Data Sheets
Publication Date
Volume
123

A new covariance data library based on ENDF/B-VII.1 was recently processed for the SCALE nuclear analysis code system. The multigroup covariance data are discussed here, along with testing and application results for critical benchmark experiments. The cross section covariance library, along with covariances for fission product yields and decay data, is used to compute uncertainties in the decay heat produced by a burned reactor fuel assembly.